FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS
Patent
·
OSTI ID:4129122
A process is given for recovering plutonium from a neutron-irradiated uranium mass (oxide or alloy) by dissolving the mass in an about equimolar alkali metalaluminum double chloride, adding aluminum metal to the mixture obtained at a temperature of between 260 and 860 deg C, and separating a uranium-containing metal phase and a plutonium-chloride- and fission-product chloridecontaining salt phase. Dissolution can be expedited by passing carbon tetrachloride vapors through the double salt. Separation without reduction of plutonium from neutron- bombarded uranium and that of cerium from uranium are also discussed.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-025580
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2948586
- OSTI ID:
- 4129122
- Country of Publication:
- United States
- Language:
- English
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